Pipe Crack Study Group - Enclosing NUREG-0531 & Notice (Generic Letter 79-14)
GL79014 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 March 15, 1979 ALL POWER REACTOR LICENSEES Gentlemen: On September 14, 1978, the Nuclear Regulatory Commission established a new Pipe Crack Study Group which was to evaluate recent pipe and safe end cracking experience relative to previous staff conclusions and recommendations. The bases for establishing the new Study Group were (1) the discovery of cracks in the inner surface of large-diameter austenitic stainless steel piping (recirculation lines) in a BWR and (2) questions concerning the capability of ultrasonic detection methods to detect small cracks. The new PCSG reviewed existing information that either was contained in written records or had been collected through meetings in this country and in foreign countries. The review was in the context of changes occurring since the preparation by the original Pipe Cracking Study Group of NUREG- 75/067 "Technical Report -- Investigation and Evaluation of Cracking in Austenitic Stainless Steel Piping of Boiling Water Reactor Plants". the conclusions and recommendations of the new Pipe Crack Study Group are presented in the enclosed "Investigation and Evaluation of Stress Corrosion Cracking in Piping of Light Water Reactor Plants", NUREG-0531. This report is for your information and comment. Also enclosed is a copy of a related Federal Register Notice. The NRC staff will review the Study Group report and its conclusions/recommendations and any comments received about the report. Following this review, the staff will decide what further actions, if any, are required for the licensing and operation of reactors. Sincerely, Brian K. Grimes, Assistant Director for Engineering and Projects Division of Operating Reactors Enclosures: 1. NUREG-0531 2. Notice
Page Last Reviewed/Updated Tuesday, March 09, 2021
Page Last Reviewed/Updated Tuesday, March 09, 2021